DocumentCode :
1617041
Title :
Progress on the 10 MW, 140 GHz ECH System for the Stellarator W7-X
Author :
Thumm, M. ; Dammertz, G. ; Gantenbein, G. ; Illy, S. ; Leonhardt, W. ; Neffe, G. ; Piosczyk, B. ; Schmid, M. ; Braune, H. ; Erckmann, V. ; Laqua, H.P. ; Michel, G. ; Weissgerber, M. ; Brand, P. ; Kasparek, W. ; Lechte, C.
Author_Institution :
Forschungszentnim Karlsruhe, Karlsruhe
fYear :
2007
Firstpage :
292
Lastpage :
292
Abstract :
Summary form only given. During the last years electron cyclotron heating (ECH) has proven to be one of the most attractive heating schemes for stellarators, as it provides net current free plasma start up and heating. Both, the stellarator Wendelstein 7-X (W7-X), which is under construction at IPP-Greifswald, Germany, and the ITER tokamak, which will be built at Cadarache, France, will be equipped with a strong EC-heating and current drive system. Both systems are similar in frequency and have CW (continuous wave) capability (140 GHz, 10 MW for W7-X and 170 GHz, 24 MW for ITER). The commissioning of the ECH plant for W7-X is well underway, the status of the project and first integrated full power test results from two modules are reported and may provide valuable input for the ITER plant. The ten gyrotrons at W7-X are arranged in two sub-groups symmetrically to a central beam duct in the ECH hall. The RF-wave of each subgroup is combined and transmitted by a purely optical multi-beam waveguide transmission line from the gyrotrons to the torus. The combination of the five gyrotron beams to two beam lines each with a power of 5 MW reduces the complexity of the system considerably. The single-beam- as well as the multi-beam waveguide mirrors and the polarizers have been manufactured. Cold tests of a full size uncooled prototype line delivered an efficiency exceeding 90%. The microwave power will be launched to the plasma through ten CVD-diamond barrier windows and in-vessel quasi-optical plug-in launchers allowing each 1 MW RF-beam to be steered independently. The polarization as well as the poloidal and toroidal launch angle can be adjusted individually to provide optimum conditions for different heating and current drive scenarios.
Keywords :
gyrotrons; plasma radiofrequency heating; stellarators; transmission lines; waveguides; CVD diamond barrier windows; Cadarache; ECH system; France; Germany; IPP Greifswald; ITER tokamak; W7-X stellarator; Wendelstein 7-X stellarator; beam polarizers; current drive system; electron cyclotron heating; frequency 140 GHz; frequency 170 GHz; gyrotrons; multibeam waveguide mirrors; optical multibeam waveguide transmission line; poloidal launch angle; power 1 MW; power 10 MW; power 24 MW; power 5 MW; quasioptical plug in launchers; radiofrequency beam steering; radiofrequency wave; single beam waveguide mirrors; stellarator heating schemes; toroidal launch angle; Cyclotrons; Electrons; Frequency; Gyrotrons; Heating; Optical waveguides; Plasma waves; Structural beams; Testing; Tokamaks;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Plasma Science, 2007. ICOPS 2007. IEEE 34th International Conference on
Conference_Location :
Albuquerque, NM
ISSN :
0730-9244
Print_ISBN :
978-1-4244-0915-0
Type :
conf
DOI :
10.1109/PPPS.2007.4345598
Filename :
4345598
Link To Document :
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